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MONTHYEARML22014A1422022-03-0808 March 2022 Regulatory Information Conference (RIC) 2022 - Be Risksmart Technical Session Polling Questions ML21181A2532021-07-0101 July 2021 Watermarked for ACRS Fc Meeting Response to Public Comments ML21109A0012021-06-0707 June 2021 NRC Staff Responses to Post-Promulgation Public Comments on RG 1.187 Revision 2 ML21092A1352021-05-0505 May 2021 Rev 2 Public Comments ACRS Version ML21092A1362021-05-0505 May 2021 Rev 4 Public Comments ACRS Version ML20349A3362021-02-28028 February 2021 Public Comment Resolution Table for DG-1321 ML20330A3282021-01-31031 January 2021 Public Comment Resolution Table for DG-1363 ML20280A7872020-12-0303 December 2020 Enclosure 2 - NRC Contact Information ML20280A7852020-12-0303 December 2020 Enclosure 1 - Proposed NRC Membership Revisions ML20220A1832020-09-21021 September 2020 Responses to Public Comments Revision 1 of Regulatory Guide (RG) 3.72, Guidance for Implementation of 10 CFR 72.48, Changes, Tests, and Experiments ML20241A0642020-08-0505 August 2020 Participant List ML20205L4022020-07-23023 July 2020 Participant List from NRC and EPRI 07/15/2020 Public Meeting ML20125A7292020-06-30030 June 2020 Public Comment Response DG-1356 for RG 1.187, Rev 2, Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments ML20182A0872020-06-30030 June 2020 Participant List ML20157A2652020-06-11011 June 2020 Gao Form - Gao for RG 1.233 ML20157A2642020-06-11011 June 2020 Gao Form - Senate for RG 1.233 ML20157A2622020-06-11011 June 2020 Gao Form - House for RG 1.233 ML20141L6142020-05-20020 May 2020 Response to Public Comments on Draft Guide 1283 - Reg Guide 1.142 Rev 3 - Safety Related Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments) ML20142A3042020-04-23023 April 2020 Participant List ML20142A3022020-04-23023 April 2020 Questions and Answers ML20083J3342020-03-12012 March 2020 HRA Data Workshop Attendess - March 2020 ML19248C6682019-12-0404 December 2019 Enclosure 2 - Alternative FHA Methodology ML19218A3432019-09-18018 September 2019 Enclosure 3 - Risk Explanations ML19219A1702019-08-0707 August 2019 PM Meeting Attendance ML19219A1682019-07-24024 July 2019 Am Meeting Attendance ML19108A4232019-03-22022 March 2019 Meeting Attendees List ML18031A8332019-02-21021 February 2019 ASME PF-1_SGHTR_Yeshnik ML18274A2882019-02-0101 February 2019 Nondisclosure Agreement Data Survey ML19046A3912019-01-23023 January 2019 Sign-In Sheet ML18220B2792018-09-17017 September 2018 DG-1336 Public Comment Resolution Table SECY-18-0090, Enclosure 1 - Plan for Addressing Potential Common Cause Failure in Digital Instrumentation and Controls2018-09-12012 September 2018 SECY-18-0090: Enclosure 1 - Plan for Addressing Potential Common Cause Failure in Digital Instrumentation and Controls ML18156A4082018-08-31031 August 2018 SECY-18-0086: Enclosure 1 - Items Reviewed by the Committee to Review Generic Requirements (CRGR) June 1, 2017, Through May 31, 2018 SECY-18-0086, Enclosure 2 - Status of Tasking Items2018-08-31031 August 2018 SECY-18-0086: Enclosure 2 - Status of Tasking Items ML18193A9912018-07-20020 July 2018 Biennial Review and Evaluation of the NRC Safety Research Program (Enclosure) ML17338A0742018-04-30030 April 2018 DG-1291 Public Comment Response ML17307A0452018-01-0808 January 2018 Enclosure - Additional Request to Make ASME Materials Available to Support Rulemaking R0 ML21039A7812017-02-28028 February 2017 SPAR Model Component Reliability Data Report-2015 Parameter Estimation Update ML17011A2022016-12-23023 December 2016 ASP Analysis-Reject-Farley TDAFW Pump Design Issue Resulted in a Degraded Condition in Both Unites(Ler 348-2015-005) ML16344A4432016-12-0606 December 2016 ASP Analysis-Reject-Final Susquehanna-HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient (LER 388-2016-005) ML16347A3252016-12-0606 December 2016 ASP Analysis-Reject-South Texas Manual Reactor Trip and Valid Auxiliary Feedwater System Actuation-LER 498-2015-001 ML16266A2302016-09-21021 September 2016 ASP Analysis Reject - Calvert Cliffs, Unit 2 Automatic Reactor Trip Due to Loss of Offsite Power to Safety Related Buses (LER-318-2015-002) ML12024A0392010-12-28028 December 2010 Pre-Decisional - Internal Draft Document; Soraca/Level 3 PRA CA Note Regulatory Guide 1.652009-07-31031 July 2009 Response to Public Comments ML0825302302009-04-13013 April 2009 Response to Public Comments for DG-1132 (Rg 1.211) ML12024A0742009-03-0909 March 2009 RES Response Comments; Don Dube Comments: Soarca Secy and Associated Enclosures ML0824902442008-10-0202 October 2008 Agreement Between the U.S. Nuclear Regulatory Commission and the Strategic Teaming and Resource Sharing Subgroup of Utilities Service Alliance, Inc. Regarding Participation in the Human Event Repository and Analysis Demonstration Project ML0813500252008-05-28028 May 2008 Final Precursor Analysis - Brunswick 2 (LER 324/06-001) ML0733801902007-06-27027 June 2007 Meeting Attendees, 6/27/07, Meeting with Firstenergy Nuclear Operating Company Regarding May 14, 2007, Demand for Information ML0614605092006-01-19019 January 2006 ADAMS Public Legacy Library Listing of TMI-2 Documents Concerning Thermocouples ML0607201462004-12-17017 December 2004 Final Precursor Analysis, LER 341/03-002, Automatic Reactor Trip and Loss of Offsite Power Due to the August 14, 2003, Transmission Grid Blackout 2022-03-08
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Draft Version for use at ACRS Full Committee Meeting on May 5, 2021 Response to Public Comments on Draft Regulatory Guide DG-1360 Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants Proposed Revision 2 of Regulatory Guide (RG) 1.205 On December 16, 2020, the NRC published a notice in the Federal Register (85 FR 73088) that Draft Regulatory Guide, DG-1360 (Proposed Revision 2 of RG 1.205), was available for public comment. The Public Comment period ended on December 31, 2020. The NRC received comments from the organizations listed below. The NRC has combined the comments and NRC staff responses in the following table.
Comments were received from the following:
Victoria K. Anderson Seth Statler Technical Advisor, Engineering & Risk Director of Government Affairs Nuclear Energy Institute (NEI) National Fire Protection Association (NFPA) 1201 F Street NW, Suite 1100 50 F Street NW Washington DC 20004 Suite 625 Agencywide Document and Management System Washington, DC, 20740 (ADAMS) Accession No. ML21007A329 ADAMS Accession No. ML21007A331
Draft Version for use at ACRS Full Committee Meeting on May 5, 2021 Commenter Section of Specific Comment NRC Resolution DG-1360 Nuclear Energy Section 3, Section 3.3 - Fire PRAs utilize processes in NUREG/CR- The NRC staff agrees with this comment Institute Pages 22-24 7150, Volume 2 on hot short induced spurious operation and made the suggested change to DG-probability and duration. 1360.
Proposed resolution:
In order to acknowledge this and provide clarification in the event of any conflicts with Section 3.3, the following statement is recommended in Section 3.3 (following the paragraph in page 4 on shorting switches):
Guidance for circuit failure mode likelihood and hot short duration for use in Fire PRAs is included in NUREG/CR-7150, Volume 2.
Nuclear Energy Section 3.1, The following statement that is included in most, if not The NRC staff agrees with this comment Institute Page 19 all, license conditions, is not included in Section 3.1. and made the suggested change to DG-This License Condition does not apply to any 1360.
demonstration of equivalency under Section 1.7 of NFPA 805.
Proposed resolution:
Recommend including that statement at the end of (1)
Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program.
Draft Version for use at ACRS Full Committee Meeting on May 5, 2021 Commenter Section of Specific Comment NRC Resolution DG-1360 National Fire Section 2.2.3 NFPA supports the NRC in providing guidance to The NRC staff agrees with this comment.
Protection licensees efforts in gaining approval for alternative Association methods prescribed by NFPA 805 but recommends that The NRC staff revised DG-1360 to add the NRC revise the language of DG-1360, 2.2.3 to include the following sentence at the end of reference to NFPA 805, 1.7. This will not only clarify the Section 2.2.3:
alignment between DG-1360 with NFPA 805 but also reinforce the incorporation of NFPA 805 into 10 CFR Licensee self-approval of fundamental 50.48. FPP changes in NFPA 805 Chapter 3 may be granted in the fire protection license condition if the alternative is functionally equivalent or adequate for the hazard as appropriate. This license condition does not apply to changes made under NFPA 805, Section 1.7, Equivalency because NFPA 805, Section 1.7 requires that those changes be submitted to and approved by the NRC.
National Fire N/A Additionally, NFPA recommends that the NRC consider The NRC staff notes this comment.
Protection making future revisions to 10 CFR 50.48(c)(4) to reduce However, the actions suggested by the Association the redundant language with NFPA 805. comment would require rulemaking, which is beyond the scope of this regulatory guide.
National Fire N/A We recommend that efforts should focus on more closely The NRC staff notes this comment.
Protection aligning 10 CFR 50.48(c)(4) with NFPA 805 and more on However, the actions suggested by the Association what licensees must include in the technical comment would require rulemaking, documentation already required by NFPA 805, 1.7 versus which is beyond the scope of this providing Special Exemptions under 10 CFR 50.12. regulatory guide.
Draft Version for use at ACRS Full Committee Meeting on May 5, 2021 Commenter Section of Specific Comment NRC Resolution DG-1360 National Fire N/A The 2020 edition of NFPA 805 is the most advanced The NRC staff notes this comment.
Protection performance-based standard for fire protection within the However, the actions suggested by the Association industry and we strongly encourage its adoption into 10 comment would require rulemaking, CFR 50.48. which is beyond the scope of this regulatory guide.